• 한국진공학회:학술대회논문집
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• 한국진공학회 2014년도 제46회 동계 정기학술대회 초록집
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• pp.241.1-241.1
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• 2014

The large-area high-power radio-frequency (RF) driven ion sources based on the negative hydrogen (deuterium) ion beam extraction are the major components of neutral beam injection (NBI) systems in future large-scale fusion devices such as an ITER and DEMO. Positive hydrogen (deuterium) RF ion sources were the major components of the second NBI system on ASDEX-U tokamak. A test large-area high-power RF ion source (LAHP-RaFIS) has been developed for steady-state operation at the Korea Atomic Energy Research Institute (KAERI) to extract the positive ions, which can be used for the NBI heating and current drive systems in the present fusion devices, and to extract the negative ions for negative ion-based plasma heating and for future fusion devices such as a Fusion Neutron Source and Korea-DEMO. The test RF ion source consists of a driver region, including a helical antenna and a discharge chamber, and an expansion region. RF power can be transferred at up to 10 kW with a fixed frequency of 2 MHz through an optimized RF matching system. An actively water-cooled Faraday shield is located inside the driver region of the ion source for the stable and steady-state operations of RF discharge. The characteristics and uniformities of the plasma parameter in the RF ion source were measured at the lowest area of the expansion bucket using two RF-compensated electrostatic probes along the direction of the short- and long-dimensions of the expansion region. The plasma parameters in the expansion region were characterized by the variation of loaded RF power (voltage) and filling gas pressure.

• Nuclear Engineering and Technology
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• 제43권4호
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• pp.391-398
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• 2011

The U metal chips generated in developing nuclear fuel and a gamma radioisotope shield have been stored under immersion of water in KAERI. When the water of the storing vessels vaporizes or drains due to unexpected leaking, the U metal chips are able to open to air. A new oxidation treatment process was raised for a long time safe storage with concepts of drying under vacuum, evaporating the containing water and organic material with elevating temperature, and oxidizing the uranium metal chips at an appropriate high temperature under conditions of controlling the feeding rate of oxygen gas. In order to optimize the oxidation process the uranium metal chips were completely dried at higher temperature than $300^{\circ}C$ and tested for oxidation at various temperatures, which are $300^{\circ}C$, $400^{\circ}C$, and $500^{\circ}C$. When the oxidation temperature was $400^{\circ}C$, the oxidized sample for 7 hours showed a temperature rise of $60^{\circ}C$ in the self-ignition test. But the oxidized sample for 14 hours revealed a slight temperature rise of $7^{\circ}C$ representing a stable behavior in the self-ignition test. When the temperature was $500^{\circ}C$, the shorter oxidation for 7 hours appeared to be enough because the self-ignition test represented no temperature rise. By using several chemical analyses such as carbon content determination, X-ray deflection (XRD), Infrared spectra (IR) and Thermal gravimetric analysis (TGA) on the oxidation treated samples, the results of self-ignition test of new oxidation treatment process for U metal chip were interpreted and supported.

• Journal of Radiation Protection and Research
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• 제42권3호
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• pp.141-145
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• 2017

Background: The concrete walls inside the vaults of cyclotron facilities are activated by neutrons emitted by the targets during radioisotope production. Reducing the amount of radioactive waste created in such facilities is very important in case they are decommissioned. Thus, we proposed a strategy of reducing the neutron activation of the concrete walls in cyclotrons during operation. Materials and Methods: A polyethylene plate and B-doped Al sheet (30 wt% of B and 2.5 mm in thickness) were placed in front of the wall in the cyclotron room of a radioisotope production facility for pharmaceutical use. The target was Xe gas, and a Cu block was utilized for proton dumping. The irradiation time, proton energy, and beam current were 8 hours, 30 MeV, and $125{\mu}A$, respectively. To determine a suitable thickness for the polyethylene plate set in front of the B-doped Al sheet, the neutron-reducing effects achieved by inserting such sheets at several depths within polyethylene plate stacks were evaluated. The neutron fluence was monitored using an activation detector and 20-g on de Au foil samples with and without 0.5-mm-thick Cd foil. Each Au foil sample was pasted onto the center of a polyethylene plate and B-doped Al sheet, and the absolute activity of one Au foil sample was measured as a standard using a Ge detector. The resulting relative activities were obtained by calculating the ratio of the photostimulated luminescence of each foil sample to that of the standard Au foil. Results and Discussion: When the combination of a 4-cm-thick polyethylene plate and B-doped Al sheet was employed, the thermal neutron rate was reduced by 78%. Conclusion: The combination of a 4-cm-thick polyethylene plate and B-doped Al sheet effectively reduced the neutron activation of the investigated concrete wall.

• 한국광학회지
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• 제13권4호
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• pp.363-369
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• 2002

디스플레이 기기에 사용할 수 있는 전도성 투과필터를 저방출(low-emissivity) 코팅인 [유전체|Ag|유전체] 구조를 이용하여 설계하였다. [$TiO_{2}$|Ti|Ag|$TiO_{2}$] 구조를 반복하고 어드미턴스 방법을 이용하여 가시광선 영역의 투과율을 높이고, 근적외선의 투과율은 낮게 하였다. 전도성 투과필터를 radio frequency(RF) 마그네트론 스퍼터링 방법으로 증착하고 설계한 스펙트럼과 비교하였으며, 필터의 광학적, 구조적, 전기적 특성들을 조사하였다. Ag 박막의 두께는 전기전도성을 높이기 위해 13㎚ 이상으로 증착하고, $TiO_{2}$박막은 가시광선 영역에서 투과율이 최대가 되는 24㎚로 증착하였다. 또한 Ag 박막의 산화를 막기 위해 매우 얇은 Ti 산화방지막을 증착하였으며, 다층구조로 갈수록 산화방지막의 두께를 더 두껍게 증착해야 하는 것을 확인하였다. 최종적으로 [$TiO_{2}$|Ti|Ag|$TiO_{2}$] 기본구조를 3번 반복하여 증착한 필터는 근적외선 차단 효과가 우수하고, 전자파 장해(electromagnetic interference; EMI)를 효과적으로 방지할 수 있는 2Ω/□ 이하의 낮은 면저항을 보였다.

• 한국산업보건학회지
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• 제26권2호
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• pp.147-158
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• 2016

Objectives: The objective of this study was to evaluate the assessment of exposure to welding fume and heavy metals among construction welders. Methods: Activity-specific personal air samplings(n=206) were carried out at construction sites of three apartment, two office buildings, and two plant buildings using PVC(poly vinyl chloride) filters with personal air samplers. The concentration of fumes and heavy metals were evaluated for five different types of construction welding jobs: general building pipefitter, chemical plant pipefitter, boiler maker, ironworker, metal finishing welder. Results: The concentration of welding fumes was highest among general building pipefitters($4.753mg/m^3$) followed by ironworkers($3.765mg/m^3$), boilermakers($1.384mg/m^3$), metal finishing welders($0.783mg/m^3$), chemical pipefitters($0.710mg/m^3$). Among the different types of welding methods, the concentration of welding fumes was highest with the $CO_2$ welding method($2.08mg/m^3$) followed by SMAW(shield metal arc welding, $1.54mg/m^3$) and TIG(tungsten inert gas, $0.70mg/m^3$). Among the different types of workplace, the concentration of welding fumes was highest in underground workplaces($1.97mg/m^3$) followed by outdoor($0.93mg/m^3$) and indoor(wall opening as $0.87mg/m^3$). Specifically comparing the workplaces of general building welders, the concentration of welding fumes was highest in underground workplaces($7.75mg/m^3$) followed by indoor(wall opening as $2.15mg/m^3$). Conclusions: It was found that construction welders experience a risk of expose to welding hazards at a level exceeding the exposure limits. In particular, for high-risk welding jobs such as general building pipefitters and ironworkers, underground welding work and $CO_2$ welding operations require special occupational health management regarding the use of air supply and exhaust equipment and special safety and health education and fume mask are necessary. In addition, there is a need to establish construction work monitoring systems, health planning and management practices.

• 한국방사선학회논문지
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• 제17권3호
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• pp.441-447
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• 2023

현재 의료방사선 분야에서 차폐를 목적으로 주로 사용되고 있는 납(Pb)소재는 방사선 차폐 기능은 뛰어 나지만 납 자체가 가지고 있는 인체 유해성과 무거운 무게에 의한 불편함 때문에 지속적으로 직, 간접적으로 방사선 피폭 위험을 차단함과 동시에 납 소재를 대체할 수 있는 인체 친화적인이며 가벼우면서 사용편의성을 가진 차폐소재의 연구는 지속적으로 진행되어지고 있다. 본 연구에서는 일반적으로 사용되는 PET(polyethylene terephthalate) 필름과 실제 방사선 방호복 사용되는 원단소재를 기재로 하여 방사선을 차폐할 수 있는 금속물질인 비스무트, 텅스텐, 주석을 스퍼터링 진공증착 방식을 통한 다층박막을 구현하여 차페필름을 제작하여 방사선 차폐소재로의 적용가능성을 평가하였다. 차폐필름을 제작하기 위한 인가전압, 롤 구동속력, 가스공급량을 제어하면서 차폐물질별 최적화된 조건을 확립하여 방사선 차폐필름 제작하였다. 모재와 차폐금속박막간 밀착력 확인은 Cross-cut 100/100으로 확인하였고 시간에 따른 박막의 변화를 측정하기 위해 내열탕 테스트 1시간을 통하여 박막의 안정성을 확인하였다. 최종적으로 구현된 차폐필름의 차폐성능은 한국방사선진흥협회를 통한 실제 방사선 차폐성능을 측정한 결과 시험조건(역넓은 빔, 관전압 50 kV, 반가층 1.828 mmAl)을 설정하여 감쇠비 16.4 (초기값 0.300 mGy/s, 측정값 0.018 mGy/s)와 감쇠비 4.31(초기값 0.300 mGy/s, 측정값 0.069 mGy/s)의 결과를 얻었다. 추후 제품화를 위한 공정효율성을 확보하여 가벼우면서 차폐성능을 보유한 필름 및 원단을 활용하여 방사선 방호복이나 차폐기능을 가진 건축자재로의 필름적용을 위한 초석을 마련하였다.